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Publications by D. T. Eash

Cryogenic Thermal Expansion of Y-12 Graphite Fuel Elements

2013English

Related publications

Fuel Elements for Ornl Graphite Reactor

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An Investigation of the Cryogenic Mechanical Properties of Low Thermal-Expansion Superalloys

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Non-Destructive Analysis of Uranium in Graphite Fuel Elements by Neutron Activation

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Fuel Development Test on Specification IV-3 ''Hi-Expansion Graphite''. Final Report

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Thermal Performance Measurements of a Graphite Tube Compact Cryogenic Support for the Superconducting Super Collider

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Thermal Behavior of Snap Reactor Fuel Elements During Atmospheric Reentry

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Development of a Process to Lower the Thermal Expansion of Hot Pressed Niobium--Graphite Composites

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Cryogenic Quad-Redundant Thermal Switch

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Time-Temperature Behavior of Fuel Elements Discharged to Air: CVI Fuel Elements

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